@inbook{4bd2f0fd8713435a8db41d2f9f9d9fa1,
title = "The thermal performance of fuel matrix material in a CO2 atmosphere",
abstract = "The thermal oxidation performance of a semi-graphitic fuel matrix-material has been compared to two grades of nuclear graphite between 600 C and 1200 C in flowing CO2. Fuel matrix material is used to produce compacts or pebbles containing TRISO coated particle fuel for High Temperature Reactors (HTRs). The A3-27 fuel matrix-material grade was compared to NBG-18 and Gilsocarbon nuclear graphite grades. At 1200 C temperatures A3-27 appears to be more reactive than NBG-18, but less so than Gilsocarbon. At 600 C the oxidation rate of A3-27 is comparable to that of NBG-18, but both are significantly higher than that of Gilsocarbon. It is concluded that the comparable thermal oxidation behaviour of graphite and fuel-matrix material suggests that operating temperatures in a CO2 cooled reactor fuelled with TRISO coated particle fuel would not need to be reduced below those considered acceptable for the use of nuclear graphite. {\textcopyright} 2013 The Authors. Published by Elsevier B.V. All rights reserved.",
author = "Joel Turner and Schmidt, {M. J S} and Abram, {T. J.}",
year = "2013",
doi = "10.1016/j.jnucmat.2013.07.012",
language = "English",
isbn = "0022-3115",
volume = "443",
series = "Journal of Nuclear Materials",
pages = "398--402",
booktitle = "Journal of Nuclear Materials",
}